Long life high efficiency neutron generator

ABSTRACT

The design of a compact, high-efficiency, high-flux capable compact-accelerator fusion neutron generator (FNG) is discussed. FNG&#39;s can be used in a variety of industrial analysis applications to replace the use of radioisotopes which pose higher risks to both the end user and national security. High efficiency, long lifetime, and high power-handling capability are achieved though innovative target materials and ion source technology. The device can be scaled up for neutron radiography applications, or down for borehole analysis or other compact applications. Advanced technologies such as custom neutron output energy spectrum, pulsing, and associated particle imaging can be incorporated.

CROSS-REFERENCE TO RELATED APPLICATIONS

This patent application claims the benefit of U.S. Provisional PatentApplication No. 61/031,899, filed Feb. 27, 2008, 61/031,908, filed Feb.27, 2008, 61/031,912, filed Feb. 27, 2008, 61/031,916 filed Feb. 27,2008, and 61/031,921, filed Feb. 27, 2008, all of which are hereinincorporated by reference in their entireties, without exclusion of anyportion thereof, whether specifically referenced herein or otherwise.

BACKGROUND OF THE INVENTION

Radioactive nuclear sources are currently used in industry in a varietyof places, including on-line elemental analysis of mining, coal, andcement feedstocks, and sub-surface scanning (e.g. soil compositionanalysis and landmine detection). The traditional neutron source hasbeen a radioisotope such as ²⁵²Cf or Am-Be. Radioisotopes are always on,require shielding, limit types of analysis (e.g. no pulsing ortime-of-flight), and pose a personnel hazard during manufacturing andassembly, as well as a security hazard due to threats of so-called“dirty bombs”. Neutrons can also be generated with conventionalaccelerator technology but these systems have large size and powerconsumption requirements. Having a compact and efficient fusion neutrongenerator (FNG) would directly benefit many industries by solving theproblems associated with radioactive isotopes while avoiding thecomplications of large accelerators.

The basic layout of a modern compact accelerator neutron source is shownin FIG. 1. The standard hardware consists of: a high-voltage generator 1(˜100 kV), a metal hydride target material 2 (usually titanium), one ormore accelerator grids 3, an ion source assembly 4 (Penning or RF) and agas-control reservoir 5 that often uses a hydrogen getter. Operationproceeds as follows: either pure deuterium (D-D system) or adeuterium-tritium (D-T system) mix of gas (up to 10 Ci of T) isintroduced into the system at pressures around 10 mTorr; a plasma isgenerated to provide ions that are extracted out of the source regionand accelerated to ˜100 keV; these ions bombard the target 2 where theycan undergo fusion reactions with other hydrogen isotopes embedded inthe target 2. DD fusion reactions generate 2.45 MeV neutrons and the DTreaction makes 14 MeV neutrons. Exemplary systems can be operatedcontinuously or in pulsed operation for time-of-flight measurements.

There are several major suppliers of non-radioactive neutron generators,all using accelerator-target configurations. List prices range between$85-350K with the highest cost components being the high-voltage powersupply, electrical feeds, and interconnects. Lifetime is typicallylimited by the degradation of the target material and the coating ofinsulators with best suppliers reporting ˜1000 hours for nominal outputlevels of 1×10⁶ DD n/s and 1×10⁸ DT n/s, and replacement target unitsrange from $5-50K each. Currently, no suppliers have cost-effective highoutput (>1E8 n/s) DD systems.

Neutron generators for industrial radioisotope replacement often use theDD fusion reaction because the 2.45-MeV DD neutrons are more easilyapplied to existing applications that use Cf²⁵², which has an averageneutron energy of 2.1 MeV. On the basis of fusion cross section andreaction branching alone, a DT generator has a neutron production rate˜100 times that of a DD generator, however, the shielding and moderationrequirements for 14.1-MeV DT-generated neutrons compared to 2.45-MeVneutrons are much more severe, making DD more attractive for many marketapplications.

BRIEF SUMMARY OF THE INVENTION

Aspects of the invention include a highly-innovative approach for acompact, high-efficiency, long-life fusion neutron generator (FNG) forapplications such as enhanced neutron radiography, non-destructivetesting, bulk material scanning using the testing process known asPrompt Gamma Neutron Activation Analysis (PGNAA), other NAA methods, andother analytical methods utilizing neutrons. Radioisotopes, such as²⁵²Cf, are currently used in the academic and industrial markets, butare under increasing scrutiny due to homeland security concerns. SeveralFNG technologies are available in the marketplace, but are hampered byhigh cost, large size, low efficiency, and short lifetime, typicallymaking them unsuitable for broad use.

As summarized in FIG. 2, an innovation for the device as a whole resultsfrom the combination of a regenerable low-Z (low atomic number) targetfor long life and high efficiency with an RF ion source that allowscompact and easy thermal management with long life. These factorscombine to increase yield and decrease cost. Improved efficiency andbetter thermal properties allow the source size to be decreased,allowing its use in applications that require small sources, such assmall-diameter boreholes (<2 inches). Such a compact and inexpensivesource could also be used in laboratory and academic settings forgeoscience and other non-destructive testing applications, such asonline bulk materials analysis (such as for coal and cement mining),soil analysis, borehole logging analysis, and security screeningsystems, and others. These innovations would allow for radioactiveneutron sources in industry to be replaced with FNGs in a wide varietyof applications, improving safety and broadening the types of analysisthat can be accomplished. Additionally, innovative designs have beenmade to combine the necessary components and subsystems of an FNG inhighly efficient and cost-effective ways.

Traditional ion sources such as a Penning ion source use activefilaments or multiple plasma-contacting electrodes to createionizations. These components eventually wear out, causing a systemfailure and limiting lifetime. Aspects of the present invention includea radio frequency (RF) or microwave ion source which uses no electrodesand has the advantage of generating high fractions of monatomic ions. AnRF ion source uses a coiled, or shaped ribbon, antenna on the outside ofthe system wall/insulator that deposits electromagnetic power into thegas, causing ionizations, dissociations and plasma sustainment. Whilecurrent FNGs bias their target to a large negative voltage to create theacceleration field, aspects of the invention use another inherentadvantage of the RF ion source and raise the voltage of the plasma whilemaintaining the RF hardware and the target at or near ground potential.This is possible because the RF couples its energy throughelectromagnetic fields instead of physical electrodes in contact withthe plasma. Using a grounded target resolves several design concerns,such as thermal control of the target and target diagnostics. This hasthe additional benefit of allowing the neutron source—the target—to becloser to the materials being analyzed due to lack of the necessaryhigh-voltage standoff hardware, resulting in higher neutron fluxes atthe material of interest for the same source output. The RF or microwaveion source also allows for relatively easy multi-source configurationswhere multiple ion beams can be extracted from a common plasma region toproduce a mutli-point neutron source.

In addition to continuous operation, several options exist for pulsedoperation. One option is to pulse an extraction electrode. This has thebenefit of requiring relatively low voltage pulses, but would stillrequire a high-voltage pulse forming network. Another option is to use apulse transformer to directly pulse the high-voltage power. A simpleschematic of a transformer-based pulsing system is shown in FIG. 7. Thisexemplary method has the advantage of allowing low-voltage pulse formingnetwork elements and a low-voltage (lower cost) DC power supply. The useof beam-bunching electrodes can further shorten pulses of a system downto the nanosecond range. The choice of pulsing technique depends on thecost, size and the needs of the end-user. All of these techniques arecapable of achieving pulse lengths in the range of 0.1-10,000 μs with acorresponding broad range of repetition rates, depending on the dutyfactor of the pulse system.

Further exemplary systems described herein can be integrated withassociated particle imaging (API) techniques.

BRIEF DESCRIPTION OF THE SEVERAL VIEWS OF THE DRAWINGS

FIG. 1 is a diagram of an exemplary modern compact accelerator neutronsource, according to an aspect of the invention;

FIG. 2 is chart illustrating the properties of different components ofan exemplary system, according to an aspect of the invention;

FIG. 3 is an exemplary neutron generator block diagram, according to anaspect of the invention;

FIG. 4 is an exemplary neutron generator, according to an aspect of theinvention;

FIG. 5 is an exemplary neutron generator with RF ion source, accordingto an aspect of the invention;

FIG. 6 is an exemplary neutron generator modified for ECR ion source,according to an aspect of the invention; and

FIG. 7 is an schematic drawing of an exemplary power pulser, accordingto an aspect of the invention.

DETAILED DESCRIPTION OF THE INVENTION

FIG. 3 shows the layout for the “neutron tube” core of a genericembodiment of the invention. A vacuum vessel 10 forms the mainstructure. Inside are the three primary electrodes: the ion source(anode) 11, neutron-producing target (cathode) 12, and electronsuppressor electrode 13. The ion source power supply 14 creates AC, DC,or radio frequency/microwave power depending on the type of ion source11 used. A non-evaporable getter 15 is used to control gas pressure viaheating.

In one possible embodiment shown in FIG. 4, the vacuum vessel 10 is asealed tube made of a combination of conductor and insulator. If one endof the neutron tube is at low voltage, it can easily be made ofconductive material facilitating fabrication and installation ofelectrical feedthroughs. Conductors used include primarily aluminum,stainless steel, copper, and kovar. Stainless steel and iron areminimized to reduce gamma signature in NAA applications. Glass, quartz,or alumina (or similar ceramic) can be used for insulated, high voltageareas. The outer diameter for this style of vacuum vessel 10 can rangefrom 0.25″ to 12″. As seen in FIG. 4, attached to the vacuum vessel 10,auxiliary to the neutron tube, can be a diagnostic pressure gauge 30,for example an ionization gauge. Electrical feedthroughs 31, 32, 33, 34,35 allow voltages to be applied to or read from to the ion source 37,suppressor 13, target 12, diagnostic thermocouple 37 and getter 15, andalso control other diagnostics and internal systems. To evacuate thevessel, a pump-out port 16 is included made of copper pinch-off tube,glass tube, or a mechanical valve 38. To fit these features within spaceconstraints, vacuum-compatible tubing 39 may be used. Pump-out port 15can be attached to metal or insulator sections of the vessel. In thecase of systems assembled completely in a vacuum environment, a pump-outport may not be needed. The body of the vacuum vessel 10 is comprised ofpre-made glass to metal or ceramic to metal seals that can be brazed orwelded together using standard metalworking or glass working techniques,and/or have two sections affixed to each other with vacuum flanges 40for easy assembly/disassembly, typically ranging in diameter from 1⅓″ to12″. During assembly the vessel 10 is pre-loaded with an appropriateamount of deuterium and/or tritium gas. For systems in output andlifetime configurations where helium buildup is a concern from theplurality of neutron-producing reactions, an ion pump style of devicecan also be attached to the vessel to pump away helium and othercontaminants after the getter 15 has temporarily pumped away the workinggas.

The ion source 36 is the anode 11 of the system that produces aplurality of ions that are accelerated into the target 12. The ion beam43 is extracted from the ion source 36, goes through an opening insuppressor 13, and finally impinges on the target 12. The amount ofextracted current should be from 10 nA/cm² to 1 kA/cm². At the front ofthe ion source 36 is an extraction plane 41 with an open diametertypically between 1 mm and 80% of the ion source 36 diameter combinedwith electrode shapes 42 that customize the focusing of the extractedion beam 43 to cover most or all of target 12. The extraction plane 41may or may not contain a gridded extraction screen with a highpercentage open area and grid spacing typically between 20 in-1 and 150in-1, dependent on plasma properties. The system may or may not have anextraction bias electrode (not shown) positioned between the ion source36 and the suppression electrode 13 to aid in extracting ion current.The ion beam 43 is shaped such that the energy density impinging on thetarget 12 is substantially uniform. This is beneficial for power/heathandling, neutron production efficiency, and target 12 lifetime. Thetype of ion source 36 used can be, but is not limited to, radiofrequency (RF) using an RF antenna 44 and matching network system 45,electron-cyclotron resonance (ECR) using microwave generator 70 to makemicrowave energy 71, Penning (cold cathode) 4, field ionization, orspark gap. The anode 11 region in vacuum may range from 1″ to 12″ long,filling either partially or completely the diameter of the vacuum vessel10 containing it.

In the case of the RF ion source, the ion source 36 is comprised of aglass container 46 (to increase monatomic species fraction relative toquartz or alumina) inside of vacuum vessel 10 (to reduce the amount ofsputtering, contamination, and ion-electron recombination compared to asteel or alumina container), RF antenna 44 (wrapped cylindrically aroundvacuum vessel 10 with 0.5 to 10 turns), magnets 47 (to make a strong,substantially uniform axial magnetic field of strength 10 Gauss to 10000Gauss inside ion source 36 to minimize power losses from plasma-wallinteractions), and RF matching network 45. Glass container 46 may beintegral to vacuum vessel 10 (for example, see vacuum vessel 72). RFpower input to the ion source 36 can range from 0.1 W to 10,000 W. TheRF frequency can be in the range of 0.1 MHz to 1 GHz. Matching network45 contains capacitors and/or inductors that can be of fixed and/oradjustable values, arranged in an “L” or “pi” configuration. Thecomponents can have the values fixed at the factory or be adjustableduring operation with a stepper motor or similar system. To furtherfine-tune matching conditions in an assembled system, the frequency atwhich the RF generator 14 operates can be adjusted in sufficiently smallincrements. The components are chosen, arranged, tuned, and fixed inplace in a relative arrangement similar to what is shown in FIG. 4 toexcite one or more modes to form and maximize plasma density and amountof extractable current, maximize monatomic species fraction in the ionbeam 43, and optimize usage of RF power. The use of an ECR ion source(see FIG. 6) can accomplish these objectives even more effectively.Typical values of frequency can range from 200 MHz to 20 GHz. Microwaveenergy can be applied to ion source with an external applicatorincluding, but not limited to, a waveguide, dielectric window, orantenna launching structure. The magnetic field is shaped to create azone of electron cyclotron resonance. The ion source 11 can be raised toa positive voltage or run at ground potential. The configuration ischosen to be appropriate for the requirements of pulsing, power level,size, and lifetime. For the embodiment in FIG. 4, the target 12 is nearground potential while the ion source 36 is raised to a high positive DCvoltage.

The electron suppressor electrode 13 works with the ion sourceextraction optics 41, 42 to shape the ion beam 43. It should be biasednegative with respect to the target (cathode) electrode 12 by an amountranging from 0 V to 10,000 V. It can be biased with a separate powersupply 21, or be biased using a resistor or zener diode system attachedto the target 12. It is sized and shaped such that field emission fromthe high voltage gradients is avoided. The outer diameter of thesuppressor 13 should substantially fill the inner diameter of vacuumvessel 10; the opening at the center should be large enough to allow theion beam 43 to pass through unobstructed, while not being so large so asto require a prohibitively large voltage difference between it and thetarget 12 to effectively suppress secondary electrons emitted from thetarget due to impinging ions. The one or more electrodes are arranged toshape an electric potential to cause a substantial fraction of ions fromthe ion source to collide with the target, to reduce electron losses toan anode electrode.

The solid target (cathode) electrode 12 consists of a cooled metalsubstrate via coolant connections 33 (also used as an electric feed if abias voltage is applied), usually stainless steel, nickel, copper ormolybdenum, that is coated with a layer of hydrogen-absorbing material,such as lithium, titanium, or others to achieve useful neutron-producingreactions. Low-Z materials are often preferable to increase efficiency.A target material may have at least one of the following properties: theaverage or effective atomic number of the target material is between 1and 21; the target material can be regenerated in situ; the targetmaterial can be deposited in situ; the target material has thecapability of causing secondary neutron-producing reactions with crosssections greater than 1 microbarn. The target may include hydrogenisotopes, lithium, lithium isotopes, lithium compounds including LiD,LiAlD₄, and LiBD₄, lithium alloys, and any mixture or combinationsthereof. The target 12 can be maintained at ground potential or biasednegative with an external power supply 17. Furthermore, the bias voltagebetween the suppressor and the target can be maintained by eitherconnecting the suppressor to a negative voltage, or grounding it, andconnecting the target to the suppressor through a zener diode, resistor,or other voltage regulation device. The size of the target 12 can bechosen appropriately for the application, power load, and lifetimeneeded. A substantially flat, circular shape is preferred, but othershapes, such as slanted, conical, or cylindrical, can be used to controlsputtered material amounts and locations (both of source anddestination) and to provide for unique neutron source emissionareas/volumes. A circular target 12 for this style of device can rangefrom 0.1″ to 12″ in diameter. A neutron tube 10 with two or more targetson either side of an ion source can be made so that two or more sourcesof neutrons are located inside of one device. Use of intentionalsputtering and evaporation inside the vacuum vessel 10, 72 can have manybenefits for system lifetime and efficiency. An attached thermocouple 37or other means of measuring temperature can be used as a diagnosticwhile in operation. The cooling system 18 of the target 12 can beelectrically isolated from the vacuum vessel 10, 72 in order to measurebeam 43 current landing on the target 12 and for other diagnosticpurposes. Active liquid cooling through channels 33 embedded in thetarget can be used for high power applications with either ambiently oractively cooled fluids. It is also possible to use a heat sink,exhausting to the surroundings. The location of the target can beanywhere beyond the suppressor electrode 13 in the path of the ion beam43, viz. near the extreme end of the system to increase neutron flux onadjacent materials under test. The surface material of the target 12 canbe deposited and/or refreshed in situ 3. Target 12 lifetime can beextended through use of regeneration. The target 12 material can also bechosen carefully to dictate the neutron output energy spectrum whilestill using deuterium and/or tritium as the working fuel. This includesmaking the system a source of fast (>2.5 MeV) neutrons without usingradioactive tritium gas.

The gas reservoir 15 can be a simple titanium filament or anon-evaporable getter pump for increased vacuum vessel 10, 72 vacuumquality. It can be located in a low-voltage area, such as behind thetarget 12, to the side of the target 12, or behind or in the ion sourceregion 36. An external power supply 19 runs ac or dc current through thedevice through an electrical feedthrough 35 to heat and control the gasreservoir's 15 temperature, thus controlling the pressure of the workinggas in the vacuum vessel 10, 72. It is loaded with an appropriate amountof deuterium and or tritium gas to achieve operating pressures between10⁻⁵ Torr and 10⁻² Torr while maintaining enough of a reserve amount ofgas to compensate for the effects of contamination and radioactive decayover time.

High voltage power supplies 17, 20 are used to separate the ion source(anode) 11, 36 and target (cathode) 12 by fusion-relevant voltages, from10 kV to greater than 500 kV. This can be accomplished with a positivevoltage supply 20 connected to the anode 11, 36, a negative voltagesupply 17 connected to the cathode 12, or both. The high voltages can begenerated though a variety of means, such as with a traditionalCockcroft-Walton voltage multiplier 73, piezoelectric crystaltransformer, or with pyroelectric crystal technology. The high voltagegeneration can be done in the generator system next to the neutron tube10 or the high voltage can be transmitted to the neutron tube via anumbilical cable 48. To help stabilize the system and reduce the effectsof accidental high-voltage arcing, over-currenting, or other problems,ballast resistance 49 may be used, which can range in value from 10 kΩto 10 MΩ.

The external enclosure 50 contains the neutron tube 10 and associatedfeedthroughs, electronics, and power supplies. It is constructed from aconducting structural material such as aluminum or stainless steel toprovide a ground shield around the entire system for safety and toprevent RF noise from affecting other equipment. The grounded enclosure50 is filled with an insulating fluid 51 for high voltage standoff andcooling, such as mineral oil, transformer oil, SF₆ gas, or a fullyfluorinated insulating fluid such as Fluorinert, which is sealed aroundthe neutron tube 10 with seal 52.

A control console may be included in the exemplary system that containsmost or all of the needed support equipment in an enclosure or rack thatprotects the equipment and makes it accessible to the user for settingand monitoring operational parameters. The system controller should behoused here, which may be comprised of a personal computer,field-programmable gate array (FPGA), or other custom or standardcircuitry. Analog and digital inputs and outputs allow the controlsystem to communicate with the other pieces of equipment, viz. the ionsource power supply (RF or microwave amplifier) 14, other power suppliesas diagrammed in FIG. 3, gas reservoir 15, and any applicable coolantsystems 18. Aspects of invention may include a plurality of diagnosticsensors selected from the group consisting of a particle detector, acurrent detector, a voltage detector, a resistivity monitor, a pressuregauge, a thermocouple, and a sputtering meter. In addition, for agrounded target, the electrode area can maximized for a given neutrontube diameter to improve longevity and tube life. The control station isconnected to the neutron tube 10 via a bundle of coaxial cables, wires,and tubing.

A preferred embodiment is detailed in FIG. 5. The vacuum envelope is asmall diameter insulating tube 72 utilizing an RF-powered ion source 36with magnet material 47. The ion source 36 is raised to high voltagewith power supply 20 (depicted as a custom-built and sizedCockcroft-Walton voltage multiplier 73 located adjacent to the neutrontube 10 so that no high voltage umbilical cables 48 are required, andfed into vacuum vessel 72 with feedthrough 74 embedded in vacuum vessel72 to bias beam-shaping electrodes (41, 42)) and the flat, circulartarget 12 is at ground potential. The suppressor 13 is biased viafeedthrough 75 embedded in vacuum vessel 72. An advanced getter material15 is loaded with D and/or T and uses a closed-loop control system 19 tomaintain stable gas pressure in the vacuum vessel 72. The target 12,comprised of a thin layer of lithium to maximize efficiency 2 andcustomize the neutron energy spectrum 5, is located on a cooledsubstrate made of a material such as nickel or molybdenum and can beregenerated 4 with heat from the ion beam 43 and through an in-situevaporation process 3 that does not require the neutron tube 72 to beopened. The target 12 is located near the extreme end of the system toplace maximum neutron flux on the objects under test. For demandingapplications where target thermal management is a necessity, such asborehole oil well logging, a grounded target 12 can be directlyheatsinked to the external enclosure 50 to efficiently transport heatgenerated by the ion beam interaction with the target to the surroundingenvironment. The external enclosure 50 is made of aluminum to minimizeNAA signals; similarly, use of carbon steel and stainless steel ingeneral is minimized. The external enclosure 50 is filled and sealedwith a fully fluorinated insulating and cooling fluid to avoid neutronmoderation and absorption by hydrogen.

FIG. 6 shows a preferred embodiment modified to use an ECR-type ionsource 36 using microwave generator 70 to make microwave energy 71,exciting gas molecules to create ionizations. Basic layouts ofcomponents auxiliary to neutron tube (10, 72) can be readily adjustedfor the device to fit within the size and shape constraints of a givenapplication.

Aspects of the invention include a neutron generator having an RF ionsource. To achieve high atomic fractions in such neutron generators(e.g. >50%) inductively coupled plasma discharges are often used.Traditionally these require kilowatt-level power for hydrogen dischargesdue to the high mobility of hydrogen ions in the plasma. As a resultintense heating and thermal cooling issues make compact devicesdifficult and expensive to engineer. For example, the prior art usessapphire windows with specialized cooling structures to managemulti-kilowatt levels and molybdenum surfaces to sustain high thermalloads.

Aspects of the invention include an approach to design the plasma sourcecavity to encourage dissociation of molecular hydrogen gas throughplasma interaction while maintaining a high degree of atomic hydrogentrapping or confinement within the plasma region for subsequentionization. This can be accomplished by using a low recombination ratesurface materials exposed to the plasma and high geometric trappingdesign of the plasma source region. Additionally, surfaces can betreated to reduce their surface recombination properties by a variety oftechniques including but not limited to, chemical etch, materialdeposition, baking, coating, and plasma treatment.

In an embodiment, the plasma source region is crafted withlow-recombination material surfaces and an exit aperture such thatdissociated hydrogen atoms will bounce around within the plasma sourcevolume with a high degree of confinement until ionization near the exitaperture for ion beam extraction. Optimization of this neutral atomictrapping can be done by shaping the ion source.

Using a magnetic mirror configuration, RF energy can be efficientlytransferred into the plasma near the exit aperture using the magneticmirror effect. RF plasma pumping can drive electrons into a highmagnetic field location and transfer axial energy into radial energy.Electrons with high radial energy ionize and dissociate hydrogen rapidlywhile low axial velocity increases local density in the high B fieldregion and produce a high-quality ion beam. The RF antenna is located inthe region of lower magnetic field such that electrons are acceleratedinto the higher B section with the RF or electromagnetic field. Theapplied RF frequency can be adjusted to maximize plasma power depositioninto the high field region in relation to the electron bounce frequencybetween the RF antenna region and the high field region. The ion sourceexit aperture is located near this region to source high currents.Combined with low-recombination materials and geometric trapping, highatomic hydrogen ion fractions and beam currents can be obtained with lowinput power levels. For a 1-inch diameter tube, currents in excess of 1mA have been obtained for power levels of less than 5 W with good atomicto molecular fractions.

The design of the magnetic mirror, B field shape and plasma sourcevolume and ion beam extraction aperture can be optimized for differentneutron generator applications, e.g. small diameter for oil-well loggingapplications, high current for neutron radiography or cargo inspectionapplications, etc. Adjusting the source profile affects the beam profileprojected onto the target. This is important for heating purposes and itis desired to have a uniform target loading. In one embodiment, themagnetic mirror is adjusted such that the ion source exit aperturemagnetic field is close to that of the field in the RF source region toproduce a highly-uniform beam at the target location.

Another embodiment of invention may include one ion source thatgenerates ions that are accelerated and collide with one or more targetmaterials each at a different target location. A further embodiment mayinclude a negative ion source.

A state-of-the-art high-efficiency ion source using a helicon RF plasmaproduces 8.1 mA of ion current using 1.24 kW of RF power for anefficiency of 6.5 microamperes per Watt of RF power. An aspect of theinvention produces at least 10 microamperes of ion current per Watt ofRF power. By enhancing the neutral atomic species trapping in the ionsource, 10 microamperes of atomic ion current per Watt of RF power canalso be attained.

All references, including publications, patent applications, andpatents, cited herein are hereby incorporated by reference to the sameextent as if each reference were individually and specifically indicatedto be incorporated by reference and were set forth in its entiretyherein.

The use of the terms “a” and “an” and “the” and similar referents in thecontext of describing the invention (especially in the context of thefollowing claims) are to be construed to cover both the singular and theplural, unless otherwise indicated herein or clearly contradicted bycontext. The terms “comprising,” “having,” “including,” and “containing”are to be construed as open-ended terms (i.e., meaning “including, butnot limited to,”) unless otherwise noted. Recitation of ranges of valuesherein are merely intended to serve as a shorthand method of referringindividually to each separate value falling within the range, unlessotherwise indicated herein, and each separate value is incorporated intothe specification as if it were individually recited herein. All methodsdescribed herein can be performed in any suitable order unless otherwiseindicated herein or otherwise clearly contradicted by context. The useof any and all examples, or exemplary language (e.g., “such as”)provided herein, is intended merely to better illuminate the inventionand does not pose a limitation on the scope of the invention unlessotherwise claimed. No language in the specification should be construedas indicating any non-claimed element as essential to the practice ofthe invention.

Preferred embodiments of this invention are described herein, includingthe best mode known to the inventors for carrying out the invention.Variations of those preferred embodiments may become apparent to thoseof ordinary skill in the art upon reading the foregoing description. Theinventors expect skilled artisans to employ such variations asappropriate, and the inventors intend for the invention to be practicedotherwise than as specifically described herein. Accordingly, thisinvention includes all modifications and equivalents of the subjectmatter recited in the claims appended hereto as permitted by applicablelaw. Moreover, any combination of the above-described elements in allpossible variations thereof is encompassed by the invention unlessotherwise indicated herein or otherwise clearly contradicted by context.

1-52. (canceled)
 53. An extended lifetime system for generatingneutrons, the system comprising: an external enclosure; a neutron tubewherein ions are produced, accelerated, and caused to collide with atleast one target material at at least one target location, the targetbeing loaded with one or more of deuterium and tritium to promotenuclear reactions to release neutrons; a vacuum vessel contained withinthe neutron tube for receiving the hydrogen isotope gas; a biasableplasma ion source driven by electromagnetic energy emitted from anexternal applicator selected from the group consisting of an RF antennaand a microwave launcher, at or near ground potential with an insulatinggap between the plasma ion source and external applicator; a cavitywherein plasma is generated and is attached to the anode electrode withat least one extraction orifice; at least one anode electrode, whereinsaid anode electrode is biased at a positive voltage with respect to theat least one target material at the at least one target location; atleast one suppression electrode biased to a negative voltage withrespect to the at least one target material at the at least one target;and one or more target electrodes including a target substrate thermallyconnected to the target material.
 54. The system according to claim 1,wherein the plasma ion source and anode electrode are operated at apositive voltage such that the target electrode is at or near groundpotential.
 55. The system according to claim 1, wherein the plasma ionsource and one or more anode electrodes are operated at a positivevoltage and the one or more target electrodes are operated at a negativevoltage with respect to ground potential.
 56. The system according toclaim 1, further comprising one or more extraction electrodes that shapeand modify ion beam characteristics for acceleration.
 57. The systemaccording to claim 1, further comprising a gas-filling port, a sealingmechanism, and a gas reservoir containing hydrogen isotopes.
 58. Thesystem according to claim 1, further comprising a plurality of sensorsand diagnostics selected from the group consisting of a charged-particledetector, a neutron detector, a photon detector, a beam sensor, acurrent detector, a voltage detector, a resistivity monitor, atemperature sensor, a pressure gauge and a sputtering meter.
 59. Thesystem according to claim 1, wherein one or more surfaces within theplasma ion source are low surface-recombination surfaces.
 60. The systemaccording to claim 1, further comprising a magnetic field producingstructure, with at least one magnet configured and located to increase amagnetic field near one or more ion beam extraction locations with apeak magnetic induction between 0.001 to 10 Tesla.
 61. The systemaccording to claim 8, wherein the magnetic field is shaped to have oneor more magnetic mirror surfaces.
 62. The system according to claim 8,wherein the electromagnetic applicator is adjusted relative to themagnetic field to achieve resonance near one or more ion beam extractionlocations.
 63. The system according to claim 8, wherein the plasma ionsource produces a majority of monatomic ions near the one or moreextraction orifices.
 64. The system according to claim 8, wherein theplasma ion source yields greater than 6.5 microamps extractable ioncurrent per Watt of electromagnetic power.
 65. The system according toclaim 1, wherein one or more extraction orifices create a plasmaextraction surface shaped to extract ions from the plasma source withouta grid or a plurality of anode electrode holes in contact with theplasma.
 66. The system according to claim 1, further comprising a targetmaterial to generate fast neutrons >3 MeV without using radioactivetritium.
 67. The system according to claim 1, wherein the negativevoltage applied to the one or more suppression electrodes is in therange of −0 V to −20,000V.
 68. The system according to claim 1, whereinthe electromagnetic applicator excitation frequency for the plasma ionsource is between 0.1 MHz to 100 GHz.
 69. The system according to claim1, wherein target degradation is mitigated in situ via one of in situdeposition, in situ regeneration or efficiency enhancement processeslimiting beam damage.
 70. The system according to claim 1, wherein theelectromagnetic applicator or one or more electrodes are pulsed.
 71. Thesystem according to claim 1, wherein one or more target electrodes arethermally-connected to one or both of a thermal management system andthe neutron tube.
 72. The system according to claim 1, wherein there isno insulation between the grounded target electrode area and the vacuumenclosure.
 73. The system according to claim 1, wherein the one or moreelectrodes create an electric potential shape adapted to cause asubstantial fraction of ions from the ion source to collide with thetarget.
 74. The system according to claim 1, further comprising adual-emission region neutron generator using a centrally-located plasmaion source with two anode electrodes generating two ion beams directedonto two separate target electrodes.
 75. A method for improving theefficiency and lifetime of a plasma ion source in a neutron generator,the method comprising: providing an ion source with one or more reducedatomic-recombination surfaces resulting from material selection andsurface treatment, and one or more constrictions that decrease the flowof neutral atomic species out of the ion source; applying a shapedmagnetic field to promote plasma confinement, energy transfer to theplasma, and increased local plasma density near one or more ion beamextraction locations; applying a extraction electrode or electrostaticfield shaping element to improve beam quality such that a substantialfraction of ions exiting the ion source are on trajectories to impingeon the target; substantially occluding metallic electrodes fromcontacting the plasma contained within the ion source to reducesputtering and erosion; operating a plasma source at or near a resonancecondition to generate a majority fraction of monatomic ions that improvethe effective energy per ion accelerated to a target location andachieve high-efficiency electromagnetic power absorption yieldingextractable ion currents greater that 6.5 microamps per Watt.